scholarly journals CALCULATION OF GAMMA-RAY ATTENUATION PARAMETERS FOR ALUMINIUM, IRON, ZIRCONIUM, AND TUNGSTEN

2020 ◽  
pp. 60-65
Author(s):  
Hiwa Mohammad Qadr
Keyword(s):  
Gamma Radiation ◽  
Free Path ◽  
Attenuation Coefficient ◽  
Gamma Ray ◽  
Mean Free Path ◽  
Mass Attenuation Coefficient ◽  
Radiation Shielding ◽  
Linear Attenuation Coefficient ◽  
Gamma Ray Attenuation ◽  
And Tungsten

The purpose of this study was to determine the linear attenuation coefficient, the mass attenuation coefficient, Half Value Layer. Tenth Value Layer and Mean Free Path for four different shielding materials such as aluminium, iron, zirconium and tungsten. By using the gamma-radiation energies emitted from 152Eu, 22Na, 137Cs, and 60Co radioactive sources. For this purpose, the attenuation measurements were performed using NaI(TI) detector. Calculated values of all parameters of the all shielding materials were compared with each other. The results of all presented parameters show that, tungsten has the best radiation shielding compared to other shielding materials. Then, the obtained parameters were compared with the theoretical values.

scholarly journals The Vital Role of La2O3 on the La2O3-CaO-B2O3-SiO2 Glass System for Shielding Some Common Gamma Ray Radioactive Sources

Materials ◽  
2021 ◽  
Vol 14 (17) ◽  
pp. 4776 ◽  
Author(s):  
Hanan Al-Ghamdi ◽  
Mengge Dong ◽  
M. I. Sayyed ◽  
Chao Wang ◽  
Aljawhara H. Almuqrin ◽  
...  
Keyword(s):  
Attenuation Coefficient ◽  
Gamma Ray ◽  
Effective Atomic Number ◽  
Mean Free Path ◽  
Mass Attenuation Coefficient ◽  
Vital Role ◽  
Radiation Shielding ◽  
Linear Attenuation Coefficient ◽  
Sio2 Glass

The role La2O3 on the radiation shielding properties of La2O3-CaO-B2O3-SiO2 glass systems was investigated. The energies were selected between 0.284 and 1.275 MeV and Phy-X software was used for the calculations. BLa10 glass had the least linear attenuation coefficient (LAC) at all the tested energies, while BLa30 had the greatest, which indicated that increasing the content of La2O3 in the BLa-X glasses enhances the shielding performance of these glasses. The mass attenuation coefficient (MAC) of BLa15 decreases from 0.150 cm2/g to 0.054 cm2/g at energies of 0.284 MeV and 1.275 MeV, respectively, while the MAC of BLa25 decreases from 0.164 cm2/g to 0.053 cm2/g for the same energies, respectively. At all energies, the effective atomic number (Zeff) values follow the trend BLa10 < BLa15 < BLa20 < BLa25 < BLa30. The half value thickness (HVL) of the BLa-X glass shields were also investigated. The minimum HVL values are found at 0.284 MeV. The HVL results demonstrated that BLa30 is the most space-efficient shield. The tenth value layer (TVL) results demonstrated that the glasses are more effective attenuators at lower energies, while decreasing in ability at greater energies. These mean free path results proved that increasing the density of the glasses, by increasing the amount of La2O3 content, lowers MFP, and increases attenuation, which means that BLa30, the glass with the greatest density, absorbs the most amount of radiation.

scholarly journals Evaluation of Gamma Radiation Attenuation Characteristics of Different Type Shielding Materials used in Nuclear Medicine Services

2019 ◽  
Vol 21 (2) ◽  
pp. 108-114
Author(s):  
Abdus Sattar Mollah
Keyword(s):  
Nuclear Medicine ◽  
Attenuation Coefficient ◽  
Gamma Ray ◽  
Mean Free Path ◽  
Mass Attenuation Coefficient ◽  
Radiation Shielding ◽  
Linear Attenuation Coefficient ◽  
Lead Glass ◽  
Storage Container ◽  
Absorbing Materials

Gamma-ray radiation shielding properties such as linear attenuation coefficient (m), mass attenuation coefficient (m/r), half- value thickness (HVT), tenth value thickness (TVL) and mean free path (MFP) were calculated for different types of radiation absorbing materials such as Concrete, Aluminum, Iron, Copper, Lead, Lead-glass and Tungsten. These materials are being widely used as radiation shielding materials in different areas of nuclear medicine facilities for different purposes. The XCOM and in-house developed computer program were used to calculate the above mentioned parameters for gamma-ray energies of 100 keV, 200 keV and 511 keV. The gamma-ray energy range used in nuclear medicine is between 100 keV and 511 keV. Results show that attenuation coefficient decreases with increase of gamma-ray energy, and attenuation coefficient increases with increase of density and shows significant variation for different materials. Linear attenuation coefficient depends on the energy of incident gamma-rays and the nature of the absorbing materials. These gamma-ray attenuation parameters of different absorbing materials can be used for proper shielding design of syringe shield, isotope storage container, isotope transport container, personnel protective shield barrier, radioactive waste storage facility etc.  in nuclear medicine services. Bangladesh J. Nuclear Med. 21(2): 108-114, July 2018  

Study on gamma ray shielding performance of concretes doped with natural sepiolite mineral

2018 ◽  
Vol 106 (12) ◽  
pp. 1009-1016 ◽  
Author(s):  
Osman Agar
Keyword(s):  
Attenuation Coefficient ◽  
Gamma Ray ◽  
Morphological Structure ◽  
Mean Free Path ◽  
Mass Attenuation Coefficient ◽  
Linear Attenuation Coefficient ◽  
Attenuation Coefficients ◽  
X Ray ◽  
Edx Analyses ◽  
Gamma Ray Attenuation

Abstract Gamma ray attenuation coefficients for various concrete types containing natural sepiolite mineral and B4C have been experimentally investigated at different gamma energies. In order to obtain the gamma rays, the four radioactive point-isotropic sources 133Ba, 137Cs, 60Co and 22Na which energies ranged from 80.9 to 1332.5 keV have been utilized. The measurements have been carried out by using HPGe detector and MCA equipped with a personal computer. The morphological structure and elemental compositions of the concretes have been measured with scanning electron microscope (SEM) and energy-dispersive X-ray (EDX) analyses. Linear attenuation coefficient (μ), mass attenuation coefficient (μm), half value layer (HVL) and mean free path (MFP) have been calculated for all concretes. The obtained results have been compared to the other materials such as Pb and Al.

Investigation and Characterization of Gamma Radiation Shielding Capacity of Heavy Minerals-Based Composite Materials

2020 ◽  
Vol 6 (4) ◽  
Author(s):  
Mohammad Asaduzzaman Chowdhury ◽  
Md. Bengir Ahmed Shuvho ◽  
Md Azizul Islam ◽  
Muhammad Borhan Uddin ◽  
Ruhul Amin Khan
Keyword(s):  
Composite Materials ◽  
Gamma Radiation ◽  
Attenuation Coefficient ◽  
Mass Attenuation Coefficient ◽  
Radiation Shielding ◽  
Integrated System ◽  
Heavy Minerals ◽  
Linear Attenuation Coefficient ◽  
Density Surface ◽  
Effects Of Radiation

Abstract Radiation shielding is an indispensable ingredient in the design of an integrated system to attenuate the effects of radiation during various operations such as space, aircraft, and nuclear plant. Discerning and exploiting the properties of composite materials compatible for radiation shielding in those applications are therefore primary obligation. In this study, we present here the results of control, ilmenite-, and garnet-based composites radiation shielding capabilities. The gamma radiation shielding competency of control, ilmenite-, and garnet-based composite materials has been examined by using linear attenuation coefficient, mass attenuation coefficient (MAC), tenth value layer (TVL), and half value layer (HVL). A comparison among those composite materials has been studied to find out the best one for radiation shielding material. Factors influencing the radiation shielding capabilities such as mechanical properties, thermal properties, density, surface morphology, and Fourier-transform infrared spectroscopy (FTIR) analysis have been studied in comparative investigations. In this work, we show that garnet-based composite material has viable radiation shielding performances as compared to the control and ilmenite-based composites. Garnet-based composite exhibits lower impact energy to withstand against gamma radiation as compared to the other tested shielding materials.

scholarly journals Experimental Investigation of Radiation Shielding Competence of Bi2O3-CaO-K2O-Na2O-P2O5 Glass Systems

Materials ◽  
2021 ◽  
Vol 14 (17) ◽  
pp. 5061
Author(s):  
Dalal Abdullah Aloraini ◽  
Aljawhara H. Almuqrin ◽  
M. I. Sayyed ◽  
Hanan Al-Ghamdi ◽  
Ashok Kumar ◽  
...  
Keyword(s):  
Attenuation Coefficient ◽  
Gamma Ray ◽  
Effective Atomic Number ◽  
Mass Attenuation Coefficient ◽  
Radiation Shielding ◽  
The Other ◽  
Linear Attenuation Coefficient ◽  
Attenuation Coefficients ◽  
Positive Effect ◽  
Theoretical Results

The gamma-ray shielding features of Bi2O3-CaO-K2O-Na2O-P2O5 glass systems were experimentally reported. The mass attenuation coefficient (MAC) for the fabricated glasses was experimentally measured at seven energy values (between 0.0595 and 1.33 MeV). The compatibility between the practical and theoretical results shows the accuracy of the results obtained in the laboratory for determining the MAC of the prepared samples. The mass and linear attenuation coefficients (MACs) increase with the addition of Bi2O3 and A4 glass possesses the highest MAC and LAC. A downward trend in the linear attenuation coefficient (LAC) with increasing the energy from 0.0595 to 1.33 MeV is found. The highest LAC is found at 1.33 MeV (in the range of 0.092–0.143 cm−1). The effective atomic number (Zeff) follows the order B1 > A1 > A2 > A3 > A4. This order emphasizes that increasing the content of Bi2O3 has a positive effect on the photon shielding proficiencies owing to the higher density of Bi2O3 compared with Na2O. The half value layer (HVL) is also determined and the HVL for the tested glasses is computed between 0.106 and 0.958 cm at 0.0595 MeV. The glass with 10 mol% of Bi2O3 has lower HVL than the glasses with 0, 2.5, 5, and 7.5 mol% of Bi2O3. So, the A4 glass needs a smaller thickness than the other glasses to shield the same radiation. As a result of the reported shielding parameters, inserting B2O3 provides lower values of these three parameters, which in turn leads to the development of superior photons shields.

Gamma radiation shielding properties of glasses within the TeO2-TiO2-ZnO system

2019 ◽  
Vol 107 (6) ◽  
pp. 517-522 ◽  
Author(s):  
M. Almatari
Keyword(s):  
Gamma Radiation ◽  
Attenuation Coefficient ◽  
Atomic Number ◽  
Effective Atomic Number ◽  
Mean Free Path ◽  
Mass Attenuation Coefficient ◽  
Radiation Shielding ◽  
Glass System ◽  
Shielding Properties ◽  
Mass Attenuation

Abstract Radiations are widely used in hospitals and health services in radiotherapy and molecular imaging using x-ray and gamma radiation which considered as the most penetrating radiations and very difficult to shield. In this study, the radiation shielding properties of different zinc oxide (ZnO) concentrations of the (95-x)TeO2-5TiO2-xZnO (x=5, 10, 15, 20, 25, 30 and 40 mol%) glass system was investigated to be introduced as a new transparency effective shielding material. In order to study shielding properties, mass attenuation coefficients in the energy range of 0.015–15 MeV photon energies for the current glass system were calculated using ParShield software. Moreover, half value layer, mean free path and effective atomic number were evaluated using the obtained attenuation coefficient. The results indicated that if ZnO was added to the current glass system the mass attenuation coefficient will be decreased as well as effective atomic number values. The highest mass attenuation coefficient at all energies was found to be in TT5Z5 glass sample as well as the effective atomic number value.

Gamma radiation shielding characteristics of some soft and hard woods of medicinal plants from Nallamala forest of Andhra Pradesh

2014 ◽  
Vol 4 (4) ◽  
pp. 150-157
Author(s):  
E. Rajasekhar ◽  
R. Jeevan Kumar ◽  
K. Venkataramaniah ◽  
K. L. Narasimham
Keyword(s):  
Medicinal Plants ◽  
Gamma Radiation ◽  
Attenuation Coefficient ◽  
Andhra Pradesh ◽  
Radiation Effects ◽  
Mass Attenuation Coefficient ◽  
Radiation Shielding ◽  
Linear Attenuation Coefficient ◽  
Relaxation Length ◽  
Medicinal Uses

Wood is a complex biomaterial useful for various applications. Wood can also be used to shield radiation from nuclear sources. In the present study, the radiation effects on various wood materials of medicinal plants collected from Nallamala forest in Andhra Pradesh, India was investigated. Gamma radiation shielding characteristics such as linear attenuation coefficient, mass attenuation coefficient, half- value thickness and relaxation length of ten different types of wood materials were measured for gamma energies 511, 662, 1173, 1275 and 1332 keV from 22Na, 137Cs and 60Co radioactive sources . Measurements were performed using a gamma spectrometer consisting of NaI (Tl) scintillation detector coupled to an 8K PC based Nuclear MCA with a good geometry set up. Classification of wood and their medicinal uses also studied. Analysis of results showed an appreciable evidence of radiation attenuation, attenuation coefficient decreasing with increase of gamma en-ergy and significant variation for different species.

Improvement of Gamma Radiation Shielding Features for Fluorophosphate Glasses Doping with Sm2O3 (PZBKNA)

2020 ◽  
Vol 15 (11) ◽  
pp. 1374-1380
Author(s):  
H. Almohiy ◽  
M. Saad ◽  
Y. M. AbouDeif ◽  
Iwona Grelowska ◽  
M. Reben ◽  
...  
Keyword(s):  
Attenuation Coefficient ◽  
Cross Sections ◽  
Radiation Safety ◽  
Effective Atomic Number ◽  
Mean Free Path ◽  
Mass Attenuation Coefficient ◽  
Radiation Shielding ◽  
Linear Attenuation Coefficient ◽  
Ordinary Concrete ◽  
Materials Used

This research reported on the radiation safety characteristics of doped fluorophosphate glasses with heavy rare earth lanthanide (Sm2O3) in the composition 40P2O5/30ZnO/20BaF2/3.8K2TeO3/1.2Al2O3/5.0Nb2O5/30000 ppm Sm2O3 and 40P2O5/30ZnO/20BaF2/3.8K2TeO3/1.2Al2O3/5.0Nb2O5/40000 ppm Sm2O3 in mol%. The parameters for shielding like that mass attenuation coefficient, MAC, linear attenuation coefficient, LAC, tenth value layers, TVL, half-value layers, HVL, effective atomic number, (Zeff), mean free path, MFP, electron density, Neff, electronic cross-sections, ECS, and total atomic cross-sections, ACS, were calculated between 0.015 and 15 MB of preparation glasses. The protection parameters of the current glasses are good in comparison to industrial materials used for nuclear shieldings, such as glass RS 253, ordinary concrete (OC), hematite serpenite (HS), or basalt magnet (BM). From the above mention results, the prepared glasses can be used as radiation safety materials.

scholarly journals Shielding Properties of Some Marble Types: A Comprehensive Study of Experimental and XCOM Results

Materials ◽  
2021 ◽  
Vol 14 (15) ◽  
pp. 4194
Author(s):  
Mohamed Elsafi ◽  
Mohamed A. El-Nahal ◽  
M. F. Alrashedi ◽  
O. I. Olarinoye ◽  
M. I. Sayyed ◽  
...  
Keyword(s):  
Attenuation Coefficient ◽  
Gamma Ray ◽  
Mean Free Path ◽  
Mass Attenuation Coefficient ◽  
Fast Neutrons ◽  
Linear Attenuation Coefficient ◽  
Protective Shield ◽  
Removal Cross Section ◽  
The Mean ◽  
Good Agreement

In this work, some marble types were collected from Egypt, and their shielding characteristics were estimated. Their rigidity, in addition to their elegant shape, led us to consider their use as a protective shield, in addition to making the workplace more beautiful. The mass attenuation coefficient (μ/ρ) was calculated for three types of marble (Breshia, Galala, and Trista) experimentally, using a narrow gamma ray source and sodium iodide scintillation detector (NaI). The results obtained were compared with the XCOM program and indicated a very good agreement between the two methods. The linear attenuation coefficient (μ) was evaluated to calculate the half and tenth value layers. The maximum value of 1.055, 1.041, and 1.024 cm−1 was obtained for Breshia, Galala, and Trista, respectively, at 0.06 MeV. The mean free path for studying the materials was compared with other shielding materials and showed good results at different energy scales. The energy absorption (EABF) and exposure buildup factors (EBF) were determined at different mean free paths. The fast neutron removal cross section ∑R was calculated and expresses the ability of the marbles to slow down fast neutrons through multiple scattering. This is the ability of the marbles to shield fast neutrons.

DETERMINATION OF THE ABSORPTION PARAMETERS OF SOME MATERIALS FOR PHOTON ENERGIES WITH NAI (TL) DETECTOR.

2020 ◽  
Vol 9 (8) ◽  
Keyword(s):  
Gamma Radiation ◽  
Layer Thickness ◽  
Attenuation Coefficient ◽  
Gamma Rays ◽  
Gamma Ray ◽  
Mass Attenuation Coefficient ◽  
Linear Attenuation Coefficient ◽  
Absorption Properties ◽  
Specific Parameter

Shielding of gamma radiation primarily involves the interaction of gamma radiation with matter. In this measurements have been made to determine the absorption parameters of Carbon, Copper and lead elemental materials of gamma-rays photons from 22Na, 137Cs and 60Co sources using the NaI (Tl) detector. The attenuation in the intensity of the beam will be determined for each varying thickness of absorber materials. Absorption properties were interpreted by means of the linear attenuation coefficient µ, mass attenuation coefficient µm , half-value layer thickness and ten value layer thickness. Among these the mass absorption coefficients is the most specific parameter because it can be specified only by gamma ray energy.

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